ML18142B272

LER 1976-19-00 for R. E. Ginna, Release of Liquid Radioactive Waste Without Continuous Operation of a Gross Activity Monitor. for R. E. Ginna, Release of Liquid Radioactive Waste Without Continuous Operation of a Gross Activity Monitor

ML18142B272
Person / Time
Site:	Ginna
Issue date:	07/16/1976
From:	White L Rochester Gas & Electric Corp
To:	O'Reilly J NRC/IE, NRC Region 1
References
LER 1976-19-00
Download: ML18142B272 (6)

Text

~~/

< lEZ~ES lllllZS PIP(l( itiiiZif t i ~

'I rr ~ 0 fa~I r

PIC J', IIAIC I

I'9 ROCHESTER GAS AND ELECTRIC CORPORATION o EAST AVENUE, ROCHESTER, N.Y. 14649 LEON O. WHITE, JR. TCI.CPHONC VICE PRESIDENT AREA COOE 7IIS 546 2700 I

July 16, 1976 Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406

Subject:

Reportable Occurrence 76-19 (14-day'eport), Release of liquid radioactive'waste without continuous operation of a gross activity monitor R. E. Qinna Nuclear Power Plant, Unit No. 1 Docket No. 50-244 Dear Mr. O'Reilly; In accordance with Technical Specifications, Article 6.9.2a, the attached report of Reportable Occurrence 76-19, 14-day, is hereby submitted. Two additional copies of this letter and the attachment are enclosed.

Very truly yours,

>."@'- 40 L. D. White, Jr.

Attachment cc: Dr. Ernst Volgenau (40)

Mr. William G. McDonald (3)

V k IP V

S I

LER 76-19/1T LICENSEE EVENT REPORT CONTROL BLOCK: (PLEA8E PRINT ALL REQUIRED INFORMATION) 1 UCENSEE LICENSE EVENT NAME UCENSE NUMBER TYPE TYPE ting' Y R E G 1 0 0 0 0 0 0 0 0 0 4 1 1 1 1 ~01.

~

7 89 14 15 25 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE DOCKET NUMBER EVENT DATE REPORT DATE

[001]coN'T T ~L 0 6 0 0 2 4 4 0 7 0 6 7 6 0 7 1 6 7 6 7 8 57 58 59 60 61 68 69 74 75 80 EVENT OESCRIPTION Qpg During reclaiming of steam generator blowdown water by processing in main water 7 8 9 80 7

[op~]

89 treatment plant demineralizers, it was determined that, from 6/17/76 to 7/6/76, ll 80

~04 releases were made from the neutralizin tank with activit ran in from less than 7 8 9 -6 80

[oOs] 2. 25xl0 to less than 3. 96x10 uCi/cc. Although activity was determined by 7 8 9 80 gg sampling prior to each release, the releases were (cont,'d. under Additional Factors) 7 8 9 PRME 80 SYSTEM CAUSE COMPONENT COMPONENT CODE CODE COMPONENT CODE SUPPER MANUFACTURER

[oa~] ~MA ~B 6 B B B H 9 9 9 Y 7 8 9 10 11 12 17 43 44 47 48 CAUSE OESCRIPTION

~os The recently installed blowdown recovery'ystem processes the blowdown water as des 7 8 9 80

~09 cribed above. The demineralizer resins concentrate the small amount of activity in the 7 89 80 Q~p] blowdown water. The resins are then regenerated and the (cont'd. on attached sheet) 7 89 FACIUTY METHOD OF 80 STATUS POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION E ~10 O NA H.P. Su ervisor review 7 8 9 10 12 13 44 45 46 80 FORM OF ACTIVITY CONTENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Q1g L M less than 0.00087 Ci Naturalizing tank to discharge canal 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION p~g ~00 o ~B NA 7 89 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION

[iiaj ~00 o NA 7 89 11 12 80 OFFSITE CONSEQUENCES Q~g Max. conc'entration in canal was 2.7xl0 -9 uCI/cc; no hazard was posed to general public 7 89 80 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION Q~g NA 7 89 10 80 PUBLICITY Q~~]

7 89 80 AooITIoNAL FAOToRs (cont'd. from Event D'escription)

@18] made without continuous use of a gross activity monitor. The blowdown has been diverted to the blowdown tank where continuous gross activity monitor is in service.

~19 (Reportable Occurrence 76-19, 14-day) .

7 89 80 NAME'uane Filkins PHQNE.716/546-2700, etx. 291-219 GPO 88 I ~ 667

~ . P 4 ~ '

/

L jfQ

"<><~o g Nor ~

@8g g p)~

Q'~ a

Licensee Event Report Reportable Occurrence 50-244/76-19 Cause Descri tion (cont'd.)

spent regenerants are collected in the neutralizing tank. This tank is then sampled and the contents analyzed for pH and activity prior to release to the discharge canal.

A temporary line has been installed to release the neutralizing tank through the liquid radioactive waste discharge monitor (R-18). An Engineering Work Request has been issued to study the possibility of installing a monitor on seco'ndary plant waste discharge and/or the installation of permanent tie in to R-18.

Car 1083 has been issued to document the corrective actions.

~ ~) '-."g r

4 P

p,